The main aim of the National Spherical Torus Experiment (NSTX) is to establish the fusion physics principles of the spherical torus (ST) concept. The NSTX device began plasma operations in February 1999 and theplasma current Ip was successfully brought up to the design value of 1 MA on 14 December 1999.The planned plasma shaping parameters, elongation κ = 1.6-2.2 and triangularity δ = 0.2-0.4, were achieved in inner walllimited, and single null and double null diverted configurations. The coaxial helicity injection(CHI) and high harmonic fast wave (HHFW) experiments were also initiated. CHI current of27 kA produced up to 260 kA toroidal current without using an ohmic solenoid. With theinjection of 2.3 MW of HHFW power, using 12 antennas connected to six transmitters, electrons were heated from a central temperature of 400 eV to 900 eV at acentral density of 3.5 × 1013 cm-3, increasing the plasma energy to 59 kJ and the toroidal β, βT, to 10%. The NBIsystem commenced operation in September 2000. The initial results with two ion sources (PNBI = 2.8 MW) show good heating, producing a total plasma stored energy of 90 kJ corresponding to βT ≈ 18% at a plasma current of 1.1 MA.